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| number = ML18059A201
| number = ML18059A201
| issue date = 02/28/2018
| issue date = 02/28/2018
| title = Oyster Creek Design Bases Assurance Inspection (Programs) Report 05000219/2018010
| title = Design Bases Assurance Inspection (Programs) Report 05000219/2018010
| author name = Dentel G T
| author name = Dentel G
| author affiliation = NRC/RGN-I
| author affiliation = NRC/RGN-I
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000219
| docket = 05000219
| license number = DPR-016
| license number = DPR-016
| contact person = Dentel G T
| contact person = Dentel G
| document report number = IR 2018010
| document report number = IR 2018010
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:Addressee (First Init UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406
{{#Wiki_filter:February 28, 2018
-2713 February 28, 2018 Mr. Bryan C. Hanson Senior Vice President, Exelon Generation Co., LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555


SUBJECT: OYSTER CREEK
==SUBJECT:==
- DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000 219/2018010 Dear Mr. Hanson
OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)  
: On February 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the Environmental Qualification Program implementation at Oyster Creek Nuclear Generating Statio The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staf The results of this inspection are documented in the enclosed repor The NRC inspectors did not identify any finding s or violation s of more-than-minor significanc This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
-rm/adams.html and the NRC
's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."


Sincerely,/RA/ Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects Docket Number:
REPORT 05000219/2018010
50-219 License Number:
 
==Dear Mr. Hanson:==
On February 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the Environmental Qualification Program implementation at Oyster Creek Nuclear Generating Station. The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
 
The NRC inspectors did not identify any findings or violations of more-than-minor significance.
 
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
 
Sincerely,
/RA/  
 
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects  
 
Docket Number: 50-219 License Number: DPR-16
 
===Enclosure:===
Inspection Report 05000219/2018010
 
==Inspection Report==
Docket Number:
50-219  
 
License Number:
DPR-16  
DPR-16  


===Enclosure:===
Report Number:
Inspection Report 05000219/2018010 cc w/encl:
05000219/2018010
Distribution via ListServ B.Hanson2
 
Enterprise Identifier: I-2018-010-0055
 
Licensee:
Exelon Generation Company, LLC
 
Facility:
Oyster Creek Nuclear Generating Station
 
Location:
Forked River, NJ
 
Inspection Dates:
January 29, 2018 to February 14, 2018
 
Inspectors:
C. Bickett, Senior Reactor Inspector
 
J. Kulp, Senior Reactor Inspector
 
J. Schoppy, Senior Reactor Inspector
 
Approved By:
G. Dentel, Chief
 
Engineering Branch 2
 
Division of Reactor Safety
 
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
 
Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
 
No findings or more-than-minor violations were identified.
 
=INSPECTION SCOPE=
 
This inspection was conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
 
==REACTOR SAFETY==
===71111.21N - Design Bases Assurance Inspection (Programs) Programs (Environmental Qualification)===
{{IP sample|IP=IP 71111.21|count=7}}
 
The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018:  
 
1) Electromatic relief valve NR-108-A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors]
 
2) Main steam isolation valve V-1-007 [solenoid valve coil and elastomers]
 
3) Core spray pump NZ01-B [motor and motor lubrication]
 
4) Narrow range drywell pressure instrument PT-642-9A [pressure transmitter, operational amplifier, and O-ring]
 
5) Primary containment electrical penetration X-31A [epoxy sealant and thermocouple cables]
 
6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring]
 
7) Reactor fuel zone level temperature element TE-56-1A [thermocouple, head gasket and silicone sealant]
 
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
 
On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staff.


SUBJECT: OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000 219/2018010 DATED FEBRUARY 28, 2018 Distribution: (e
=DOCUMENTS REVIEWED=
-mail) DCollins, RA DLew, DRA MGray, DRP DPelton, DRP BWelling, DRS JYerokun, DRS MYoung, BC SShaffer, DRP CSafouri, DRP APatel, SRI EAndrews, DRP, RI GDentel, DRS CBickett, DRS KMcKenzie, DRP JBowen, RI, OEDO RidsNrrPMOysterCreek Resource RidsNrrDorlLpl1 Resource


ROPreports Resource DOCUMENT NAME:
71111.21N
G:\DRS\Engineering Branch 2
Procedures
\Environmental Qualification (EQ)
2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation,
\EQ Insp Reports (Region 1 only)\Oyster Creek EQ IR 2018010.docx ADAMS ACCESSION NUMBER: ML18059A201 SUNSI ReviewNon-SensitiveSensitivePublicly AvailableNon-Publicly AvailableOFFICE RI/DRS RI/DRP RI/DRS NAME CBickett MYoung GDentel DATE 02/22/18 02/22/18 02/2818 OFFICIAL RECORD COPY
Revision 25
610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In-Service Test, Revision 72
665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15
EMG-3200.01A-FC, RPV Control - No ATWS EOP Flowchart, Revision 10
MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5
PES-S-002, Shelf Life, Revision 8
SM-AA-102, Warehouse Operations, Revision 24
Issue Reports (*initiated in response to inspection)
280415
354622
354637
554544
756924
844027
847413
2399
875631
880917
893317
911682
983859
1008809
1147890
26157
1518358
1568796
1680592
2394239
2397876
24903
2532305
2567167
2640145
3946707
3975833
3998185
3998203
3998203
4065078
4074271
4074273
4075139
4080517
4086301
4099394
4098406*
4099776*
4099904*
4103093*
4103107*


1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 50-219 License Number: DPR-16 Report Number: 05000219/2018010 Enterprise Identifier:
Equipment Qualification Files
I-2018-010-0055 Licensee:
OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8
Exelon Generation Company, LLC Facility:
OC-302, Dresser Controllers, Model 1539VX, Revision 6
Oyster Creek Nuclear Generating Station Location:
OC-303, General Electric Electrical Penetrations, Model F01, Revision 5
Forked River, NJ Inspection Dates: January 29, 2018 to February 14, 2018 Inspectors:
OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5
C. Bickett, Senior Reactor Inspector J. Kulp, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector Approved By:
OC-306, General Electric Motor Control Center (MCC), Model IC-7700, Revision 5
G. Dentel
OC-307, General Electric Pump Motor, Revision 9
, Chief Engineering Branch 2 Division of Reactor Safety 2 SUMMARY The U.S. Nuclear Regulatory Commission (
OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6
NRC) continued monitoring Exelon's performance at Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Proces The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactor Refer to https://www.nrc.gov/reactors/operating/oversight.html for more informatio No findings or more
OC-323, Barksdale Pressure Switches, Revision 7
-than-minor violations were identifie INSPECTION SCOPE This inspection w as conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise note Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading
OC-353, Solenoid Valves, Revision 4
-rm/doc-collections/insp
OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6
-manual/inspection
OC-365, PYCO Temperature Elements, Revision 6
-procedure/index.htm Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light
OC-392, Patel Electrical Connectors, Revision 7
-Water Reactor Inspection Program - Operations Phase."
OC-396, Raychem Cable Splice, Revision 7
Test Reports
EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical
Connectors Model 841203-7-12, dated 9/15/00
EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06


The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standard REACTOR SAFETY 71111.21N - Design Bases Assurance Inspection (Programs) Programs (Environmental Qualification)
EPRI Report 1016272, Turbine Oil Compatibility - Mobil DTE 372: Addition of New Generation
(7 Samples) The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018: 1) Electromatic relief valve NR
Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008
-108-A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors
EPRI Report 1019593, Radiation Stability of Modern Turbine Oils - Group II Turbine Oils
] 2) Main steam isolation valve V
Exposed to Loss-of-Coolant Accident Radiation, September 2009
-1-007 [solenoid valve coil and elastomers
GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation,
] 3) Core spray pump NZ01
November 1991
-B [motor and motor lubrication]
PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by
4) Narrow range drywell pressure instrument PT
Patel Engineers for use in Nuclear Power Plants, dated 5/5/86
-642-9A [pressure transmitter, operational amplifier, and O-ring] 5) Primary containment electrical penetration X
PEP No. 42963, Project Engineer Program Test - Dresser Relief Valve Actuator, dated 6/11/68
-31A [epoxy sealant and thermocouple cables
R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A,
] 6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring] 7) Reactor fuel zone level temperature element TE
581A, and 583A Differential Pressure Switches, dated 12/22/83
-56-1A [thermocouple, head gasket and silicone sealant
Report No. 45592-3, Nuclear Environmental Qualification Test Program on Rosemount 1153
]
Series D Pressure Transmitters, dated 5/4/83
3 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this repor On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staf DOCUMENTS REVIEWED 71111.21N Procedures 2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation, Revision 25 610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In
Report No. 46882-0, Performance and Recertification Testing of Dresser Electromatic relief
-Service Test, Revision 72 665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15 EMG-3200.01A-FC, RPV Control
Valve (Type 1525VX-3) for GPU Nuclear, Inc., dated 2/11/99
- No ATWS EOP Flowchart, Revision 10 MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5 PES-S-002, Shelf Life, Revision 8 SM-AA-102, Warehouse Operations, Revision 24 Issue Reports (*initiated in response to inspection)
Report No. 58442-1, Environmental Qualification Test Report of Raychem WCSF-N Nuclear
280415 354622 354637 554544 756924 844027 847413 862399 875631 880917 893317 911682 983859 1008809 1147890 1426157 1518358 1568796 1680592 2394239 2397876 2424903 2532305 2567167 2640145 3946707 3975833 3998185 3998203 3998203 4065078 4074271 4074273 4075139 4080517 4086301 4099394 4098406* 4099776* 4099904* 4103093* 4103107* Equipment Qualification Files OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8 OC-302, Dresser Controllers, Model 1539VX, Revision 6 OC-303, General Electric Electrical Penetrations, Model F01, Revision 5 OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5 OC-306, General Electric Motor Control Center (MCC), Model IC
In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80
-7700, Revision 5 OC-307, General Electric Pump Motor, Revision 9 OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6 OC-323, Barksdale Pressure Switches, Revision 7 OC-353, Solenoid Valves, Revision 4 OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6 OC-365, PYCO Temperature Elements, Revision 6 OC-392, Patel Electrical Connectors, Revision 7 OC-396, Raychem Cable Splice, Revision 7 Test Reports EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical Connectors Model 841203
Report No. 58722-2, Environmental Qualification Test Report of Raychem WCSF-N Nuclear
-7-12, dated 9/15/00 EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06
In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82
Work Orders
00028865
00028866
04348666
04357851
04584366
04682332
04688852
04700696
04712762
057890
510614
C0551610
C2013622
R2027147
R2060096
R2068283
R2094168
R2094317
R2119989
R2128488
R2132376
R2133635
R2134243
R2139132
R2145456
R2158529
R2173050
R2211760
R2215539
R2246426
Calculations
C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1
C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy
Calculation, Revision 0
C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study,
Revision 3
C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0
GENE-0000-0027-3965, Similarity Analysis - DD233A3620P001 vs. CR9503-213CAT55
Solenoids, dated 3/26/04
Report No. 02-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks,
Revision 0
Drawings
2-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84
846D986, Sheet 1, Penetration Seal TH, Revision 5
GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35
GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout - RB 51, Revision 0
GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2
GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4
Operating Experience
NRC Bulletin 90-01, Supplement 1, Loss of Fill-Oil in Transmitter Manufactured by Rosemount,
dated 12/22/92
NRC Information Notice 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters,
dated 4/21/89


4 EPRI Report 1016272, Turbine Oil Compatibility
Vendor Manuals
- Mobil DTE 372: Addition of New Generation Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008 EPRI Report 1019593, Radiation Stability of Modern Turbine Oils
VM-OC-0002, 24 Main Steam Isolation Valve, Revision 10
- Group II Turbine Oils Exposed to Loss
VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4
-of-Coolant Accident Radiation, September 2009 GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation, November 1991 PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by Patel Engineers for use in Nuclear Power Plants, dated 5/5/86 PEP No. 42963, Project Engineer Program Test
VM-OC-0039, PYCO Temperature Elements, Revision 2
- Dresser Relief Valve Actuator, dated 6/11/68 R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A, 581A, and 583A Differential Pressure Switches, dated 12/22/83 Report No. 45592
VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11
-3, Nuclear Environmental Qualification Test Program on Rosemount 1153 Series D Pressure Transmitters, dated 5/4/83 Report No. 46882
VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6
-0, Performance and Recertification Testing of Dresser Electromatic relief Valve (Type 1525VX
VM-OC-0285, ITT Barton Model 580 A-0 DPIS, Revision 5
-3) for GPU Nuclear, Inc., dated 2/11/99 Report No. 58442
VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with
-1, Environmental Qualification Test Report of Raychem WCSF
Model 224C DPU, Revision 5
-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80 Report No. 58722
VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical
-2, Environmental Qualification Test Report of Raychem WCSF
Connector, Revision 1
-N Nuclear In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82 Work Orders 00028865 00028866 04348666 04357851 04584366 04682332 04688852 04700696 04712762 057890 510614 C0551610 C2013622 R2027147 R2060096 R2068283 R2094168 R2094317 R2119989 R2128488 R2132376 R2133635 R2134243 R2139132 R2145456 R2158529 R2173050 R2211760 R2215539 R2246426 Calculations C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1 C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy Calculation, Revision 0 C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study, Revision 3 C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0 GENE-0000-0027-3965, Similarity Analysis
VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3
- DD233A3620P001 vs. CR9503
VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2
-213CAT55 Solenoids, dated 3/26/04 Report No. 02
VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH-3160),
-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks, Revision 0 Drawings 102-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84 846D986, Sheet 1, Penetration Seal 'TH', Revision 5 GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35 GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout
Revision 8
- RB 51', Revision 0 GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2 GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4 Operating Experience NRC Bulletin 90
VM-OC-6379, GEK-13903 Penetration Seals, Revision 0
-01, Supplement 1, Loss of Fill
Miscellaneous
-Oil in Transmitter Manufactured by Rosemount, dated 12/22/92 NRC Information Notice 89
21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification
-42, Failure of Rosemount Models 1153 and 1154 Transmitters, dated 4/21/89 5 Vendor Manuals VM-OC-0002, 24" Main Steam Isolation Valve, Revision 10 VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4 VM-OC-0039, PYCO Temperature Elements, Revision 2 VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11 VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6 VM-OC-0285, ITT Barton Model 580 A
Reference Manual, Revision 1
-0 DPIS, Revision 5 VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with Model 224C DPU, Revision 5 VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical Connector, Revision 1 VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3 VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2 VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH
21A5477, Relief Valve Specification, Revision 0
-3160), Revision 8 VM-OC-6379, GEK
619.3.005, High Flow in the Main Steam Line Test and Calibration, performed 10/2/17
-13903 Penetration Seals, Revision 0 Miscellaneous 1021067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1 21A5477, Relief Valve Specification, Revision 0 619.3.005, High Flow in the Main Steam Line Test and Calibration, performed 10/2/17 DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor Evaluation, dated 12/4/98 ECR ECP 15
DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor
-00376, Core Spray Motor P
Evaluation, dated 12/4/98
-20-1B As-Is Acceptance of Vibration ECR IEC 10-00401, Canadian Core Spray Pump Motor EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87, and 3/30/88 ES-027, Environmental Parameters  
ECR ECP 15-00376, Core Spray Motor P-20-1B As-Is Acceptance of Vibration
- Oyster Creek NGS, Revision 4 Five-Year Vibration Trend Plots  
ECR IEC 10-00401, Canadian Core Spray Pump Motor
- NZ01B Core Spray Main Motor P
EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87,
-20-1B LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical Equipment Important to Safety  
and 3/30/88
- Oyster Creek Nuclear Generating Station, dated 5/28/85 OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray Pump NZ01
ES-027, Environmental Parameters - Oyster Creek NGS, Revision 4
-B Maintenance Strategy NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of Limited Life Items, dated May 1992 NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990 NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications NRC Inspection Report 05000219/86
Five-Year Vibration Trend Plots - NZ01B Core Spray Main Motor P-20-1B
-08 (EQ Program Implementation), dated 8/8/86 OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain Installation, Revision 0 OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17 OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS
LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical
-RE0022A Maintenance Strategy, dated 6/7/17 OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17 Oyster Creek EQ Master List, dated 1/8/14 Pre-NRC EQ DBA Self
Equipment Important to Safety - Oyster Creek Nuclear Generating Station, dated
-Assessment, dated 11/13/17 (AR 03966720)
5/28/85
SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System, Revision 3 SE No. 000210
OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray Pump NZ01-B Maintenance Strategy
-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13 Level Transmitters Safety Evaluation, Revision 0 SE No. 315403
NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of
-019, Drywell Design Pressure Reduction  
Limited Life Items, dated May 1992
- Tech Spec Change, Revision 1 SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0 TDR 1003, Environmental Qualification 'Sound Reasons to the Contrary' Guidelines, Revision 0
NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990
NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications
NRC Inspection Report 05000219/86-08 (EQ Program Implementation), dated 8/8/86
OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain
Installation, Revision 0
OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17
OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS-RE0022A Maintenance
Strategy, dated 6/7/17
OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17
Oyster Creek EQ Master List, dated 1/8/14
Pre-NRC EQ DBA Self-Assessment, dated 11/13/17 (AR 03966720)
SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System,
Revision 3
SE No. 000210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13
Level Transmitters Safety Evaluation, Revision 0
SE No. 315403-019, Drywell Design Pressure Reduction - Tech Spec Change, Revision 1
SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0
TDR 1003, Environmental Qualification Sound Reasons to the Contrary Guidelines, Revision 0
}}
}}

Latest revision as of 07:53, 6 January 2025

Design Bases Assurance Inspection (Programs) Report 05000219/2018010
ML18059A201
Person / Time
Site: Oyster Creek
Issue date: 02/28/2018
From: Glenn Dentel
NRC Region 1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Dentel G
References
IR 2018010
Download: ML18059A201 (7)
v • d • e


Text

February 28, 2018

SUBJECT:

OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)

REPORT 05000219/2018010

Dear Mr. Hanson:

On February 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the Environmental Qualification Program implementation at Oyster Creek Nuclear Generating Station. The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any findings or violations of more-than-minor significance.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects

Docket Number: 50-219 License Number: DPR-16

Enclosure:

Inspection Report 05000219/2018010

Inspection Report

Docket Number:

50-219

License Number:

DPR-16

Report Number:

05000219/2018010

Enterprise Identifier: I-2018-010-0055

Licensee:

Exelon Generation Company, LLC

Facility:

Oyster Creek Nuclear Generating Station

Location:

Forked River, NJ

Inspection Dates:

January 29, 2018 to February 14, 2018

Inspectors:

C. Bickett, Senior Reactor Inspector

J. Kulp, Senior Reactor Inspector

J. Schoppy, Senior Reactor Inspector

Approved By:

G. Dentel, Chief

Engineering Branch 2

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

No findings or more-than-minor violations were identified.

INSPECTION SCOPE

This inspection was conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21N - Design Bases Assurance Inspection (Programs) Programs (Environmental Qualification)

Main article: IP 71111.21

The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018:

1) Electromatic relief valve NR-108-A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors]

2) Main steam isolation valve V-1-007 [solenoid valve coil and elastomers]

3) Core spray pump NZ01-B [motor and motor lubrication]

4) Narrow range drywell pressure instrument PT-642-9A [pressure transmitter, operational amplifier, and O-ring]

5) Primary containment electrical penetration X-31A [epoxy sealant and thermocouple cables]

6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring]

7) Reactor fuel zone level temperature element TE-56-1A [thermocouple, head gasket and silicone sealant]

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staff.

DOCUMENTS REVIEWED

71111.21N

Procedures

2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation,

Revision 25

610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In-Service Test, Revision 72

665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15

EMG-3200.01A-FC, RPV Control - No ATWS EOP Flowchart, Revision 10

MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5

PES-S-002, Shelf Life, Revision 8

SM-AA-102, Warehouse Operations, Revision 24

Issue Reports (*initiated in response to inspection)

280415

354622

354637

554544

756924

844027

847413

2399

875631

880917

893317

911682

983859

1008809

1147890

26157

1518358

1568796

1680592

2394239

2397876

24903

2532305

2567167

2640145

3946707

3975833

3998185

3998203

3998203

4065078

4074271

4074273

4075139

4080517

4086301

4099394

4098406*

4099776*

4099904*

4103093*

4103107*

Equipment Qualification Files

OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8

OC-302, Dresser Controllers, Model 1539VX, Revision 6

OC-303, General Electric Electrical Penetrations, Model F01, Revision 5

OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5

OC-306, General Electric Motor Control Center (MCC), Model IC-7700, Revision 5

OC-307, General Electric Pump Motor, Revision 9

OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6

OC-323, Barksdale Pressure Switches, Revision 7

OC-353, Solenoid Valves, Revision 4

OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6

OC-365, PYCO Temperature Elements, Revision 6

OC-392, Patel Electrical Connectors, Revision 7

OC-396, Raychem Cable Splice, Revision 7

Test Reports

EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical

Connectors Model 841203-7-12, dated 9/15/00

EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06

EPRI Report 1016272, Turbine Oil Compatibility - Mobil DTE 372: Addition of New Generation

Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008

EPRI Report 1019593, Radiation Stability of Modern Turbine Oils - Group II Turbine Oils

Exposed to Loss-of-Coolant Accident Radiation, September 2009

GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation,

November 1991

PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by

Patel Engineers for use in Nuclear Power Plants, dated 5/5/86

PEP No. 42963, Project Engineer Program Test - Dresser Relief Valve Actuator, dated 6/11/68

R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A,

581A, and 583A Differential Pressure Switches, dated 12/22/83

Report No. 45592-3, Nuclear Environmental Qualification Test Program on Rosemount 1153

Series D Pressure Transmitters, dated 5/4/83

Report No. 46882-0, Performance and Recertification Testing of Dresser Electromatic relief

Valve (Type 1525VX-3) for GPU Nuclear, Inc., dated 2/11/99

Report No. 58442-1, Environmental Qualification Test Report of Raychem WCSF-N Nuclear

In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80

Report No. 58722-2, Environmental Qualification Test Report of Raychem WCSF-N Nuclear

In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82

Work Orders

00028865

00028866

04348666

04357851

04584366

04682332

04688852

04700696

04712762

057890

510614

C0551610

C2013622

R2027147

R2060096

R2068283

R2094168

R2094317

R2119989

R2128488

R2132376

R2133635

R2134243

R2139132

R2145456

R2158529

R2173050

R2211760

R2215539

R2246426

Calculations

C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1

C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy

Calculation, Revision 0

C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study,

Revision 3

C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0

GENE-0000-0027-3965, Similarity Analysis - DD233A3620P001 vs. CR9503-213CAT55

Solenoids, dated 3/26/04

Report No. 02-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks,

Revision 0

Drawings

2-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84

846D986, Sheet 1, Penetration Seal TH, Revision 5

GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35

GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout - RB 51, Revision 0

GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2

GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4

Operating Experience

NRC Bulletin 90-01, Supplement 1, Loss of Fill-Oil in Transmitter Manufactured by Rosemount,

dated 12/22/92

NRC Information Notice 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters,

dated 4/21/89

Vendor Manuals

VM-OC-0002, 24 Main Steam Isolation Valve, Revision 10

VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4

VM-OC-0039, PYCO Temperature Elements, Revision 2

VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11

VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6

VM-OC-0285, ITT Barton Model 580 A-0 DPIS, Revision 5

VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with

Model 224C DPU, Revision 5

VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical

Connector, Revision 1

VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3

VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2

VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH-3160),

Revision 8

VM-OC-6379, GEK-13903 Penetration Seals, Revision 0

Miscellaneous

21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification

Reference Manual, Revision 1

21A5477, Relief Valve Specification, Revision 0

619.3.005, High Flow in the Main Steam Line Test and Calibration, performed 10/2/17

DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor

Evaluation, dated 12/4/98

ECR ECP 15-00376, Core Spray Motor P-20-1B As-Is Acceptance of Vibration

ECR IEC 10-00401, Canadian Core Spray Pump Motor

EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87,

and 3/30/88

ES-027, Environmental Parameters - Oyster Creek NGS, Revision 4

Five-Year Vibration Trend Plots - NZ01B Core Spray Main Motor P-20-1B

LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical

Equipment Important to Safety - Oyster Creek Nuclear Generating Station, dated

5/28/85

OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray Pump NZ01-B Maintenance Strategy

NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of

Limited Life Items, dated May 1992

NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990

NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications

NRC Inspection Report 05000219/86-08 (EQ Program Implementation), dated 8/8/86

OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain

Installation, Revision 0

OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17

OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS-RE0022A Maintenance

Strategy, dated 6/7/17

OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17

Oyster Creek EQ Master List, dated 1/8/14

Pre-NRC EQ DBA Self-Assessment, dated 11/13/17 (AR 03966720)

SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System,

Revision 3

SE No. 000210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13

Level Transmitters Safety Evaluation, Revision 0

SE No. 315403-019, Drywell Design Pressure Reduction - Tech Spec Change, Revision 1

SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0

TDR 1003, Environmental Qualification Sound Reasons to the Contrary Guidelines, Revision 0

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